多群输运-燃耗耦合蒙特卡罗计算(英文)  

Multigroup Monte Carlo Calculation Coupled of Transport and Burnup

作　　者：邓力[1] 谢仲生[2] 李树[1] 

机构地区：[1]北京应用物理与计算数学研究所计算物理实验室,北京100088 [2]西安交通大学核能科学工程系,陕西西安710049

出　　处：《计算物理》2003年第1期65-70,共6页Chinese Journal of Computational Physics

基　　金：SupportedbytheScienceFoundationofChinaAcademyofEngineeringPhysicsundertheGrantNo .2 0 0 10 660

摘　　要：介绍三维多群中子输运 燃耗耦合P3近似蒙特卡罗程序MCMG BURN .该程序是在连续截面蒙特卡罗程序MCNP和反应堆栅元均匀化程序WIMS基础上发展而来的 .使用多群截面库模拟临界实验堆和高通量工程实验堆 ,取得了与MCNP和实验一致的结果 .MCMG BURN具有与MCNP相同的精度 ,但计算时间较MCNP要少得多 .A 3\|D multigroup P\-3 approximation Monte Carlo code MCMG\|BURN is developed by coupling the neutron transport and burnup.MCMG\|BURN code is based on the continuous\|energy cross\|section Monte Carlo code MCNP and the lattice homogeneous code WIMS.It uses the multigroup cross\|section libraries to simulate the critical test reactors and HFETR(High Flux Engineering Test Reactor).The agreement results with the MCNP results and experiments are achieved.The MCMG\|BURN code is at almost the same precision with the MCNP code while requiring considerably less computing time.

关 键 词：耦合 计算 三维多群 P3近似 蒙特卡罗 中子输运 燃耗 核反应堆 

分 类 号：TL329.2[核科学技术—核技术及应用]